Volumes | International Conference on Nuclear Engineering | American Society of Mechanical Engineers Digital Collection

Topics: Radioactive wastes , Safety , Pacific Ocean , Ocean waste disposal , Accidents , Collaboration , Fukushima nuclear disaster, Japan, 2011 , Nuclear power , Seabed , Seas

Fast On-Line Source Term Estimation of Non-Constant Releases in Nuclear Accident Scenario Using Extended Kalman Filter

Pierre Tricard, Sheng Fang, Jianlong Wang, Hong Li, Jingyuan Qu, Jiejuan Tong, Dong Fang

ICONE 2013; V003T06A004https://doi.org/10.1115/ICONE21-15125

Abstract

View Articletitled, Fast On-Line Source Term Estimation of Non-Constant Releases in Nuclear Accident Scenario Using Extended Kalman Filter

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Topics: Accidents , Kalman filters , Algorithms , Errors , Emergency response , Emissions , Radioactive substances , Robustness

Analysis of Factors Influencing Compressive Bearing Capacity of Nuclear Containment

Gangling Hou, Chenning Song, Tianshu Song, Guoliang Zhou

ICONE 2013; V003T06A005https://doi.org/10.1115/ICONE21-15191

Abstract

View Articletitled, Analysis of Factors Influencing Compressive Bearing Capacity of Nuclear Containment

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Topics: Containment , Load bearing capacity , Steel , Tendons

Live Experimental Results of Melt Pool Behaviour in the PWR Lower Head With Insulated Upper Lid and External Cooling

Xiaoyang Gaus-Liu, Alexei Miassoedov

ICONE 2013; V003T06A006https://doi.org/10.1115/ICONE21-15204

Abstract

View Articletitled, Live Experimental Results of Melt Pool Behaviour in the PWR Lower Head With Insulated Upper Lid and External Cooling

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Topics: Cooling , Pressurized water reactors , Heat flux , Vessels , Boundary-value problems , Critical heat flux , Heat transfer , Temperature , Accident management , Accidents

The Human Reliability Analysis in Fire PSA Using Spar-H Method

Yao Wang

ICONE 2013; V003T06A007https://doi.org/10.1115/ICONE21-15242

Abstract

View Articletitled, The Human Reliability Analysis in Fire PSA Using Spar-H Method

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Topics: Fire , Human reliability analysis , Spar platforms , Wing spars , Nuclear power stations , Fire risk , Nuclear industry , Probabilistic safety assessment , Risk

Research for Crossing Strait Transportation Accident of Nuclear Fuel Assemblies

Xiaoxiao Xu, Xuexin Wang, Jiangang Zhang, Chaoduan Li, Gao Fan, Rongyao Tang, Lian Cao, Bing Wen

ICONE 2013; V003T06A008https://doi.org/10.1115/ICONE21-15253

Abstract

View Articletitled, Research for Crossing Strait Transportation Accident of Nuclear Fuel Assemblies

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Topics: Accidents , Nuclear fuels , Transportation systems , Ships , Collisions (Physics) , Fire , Nuclear power stations , Seas , Fuels , Hazards

Reliability Analysis for Power Supply System in a Typical Reprocessing Facility Based on GO Methodology

Renze Wang, Zongyang Feng, Pengbo Li

ICONE 2013; V003T06A009https://doi.org/10.1115/ICONE21-15258

Abstract

View Articletitled, Reliability Analysis for Power Supply System in a Typical Reprocessing Facility Based on GO Methodology

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Topics: Event history analysis , Reliability , Modeling , China , Nuclear industry , Safety , Spent nuclear fuels , Stability

The Research on Core Melting Process: Oxidation

Jun Wang, Wenxi Tian, Jianan Lu, Yingying Ma, Guanghui Su, Suizheng Qiu

ICONE 2013; V003T06A010https://doi.org/10.1115/ICONE21-15268

Abstract

View Articletitled, The Research on Core Melting Process: Oxidation

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Topics: Melting , Oxidation , Accidents , Cladding systems (Building) , Fuel rods , Coolants , Design , Flow (Dynamics) , Rupture , Delays

PSA Conservatism Analysis and Quantification for the LOFW Accident

Tony X. Kong, Chunrui Deng, Ivan Vrbanic, Ivica Basic

ICONE 2013; V003T06A011https://doi.org/10.1115/ICONE21-15299

Abstract

View Articletitled, PSA Conservatism Analysis and Quantification for the LOFW Accident

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Topics: Accidents , Uncertainty , Sensitivity analysis , Feedwater , Pressurized water reactors , Probabilistic safety assessment , Safety , Statistical distributions

First-Order and Second-Order Sensitivity Studies of ARCON96 for Ground Release Mode

Yun Liu, Sheng Fang, Hong Li, Dong Fang, Jiejuan Tong, Jingyuan Qu

ICONE 2013; V003T06A012https://doi.org/10.1115/ICONE21-15307

Abstract

View Articletitled, First-Order and Second-Order Sensitivity Studies of ARCON96 for Ground Release Mode

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Topics: Approximation , Control rooms , Design , Nuclear power stations , Robustness , Stability , Wind velocity

Study on the Influence of Safety Injection Rate on the Process of SBLOCA

He Hui, Liang-ming Pan

ICONE 2013; V003T06A013https://doi.org/10.1115/ICONE21-15314

Abstract

View Articletitled, Study on the Influence of Safety Injection Rate on the Process of SBLOCA

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Topics: Heat transfer , Safety

Sensitivity Studies on the Influence of Shutdown Control Assembly Banks Arrangement in Rod Control Assembly Banks Withdrawal From a Subcritical Condition

Dawei Cui, Yanhua Cheng, Yulong Mao, Jun Chen

ICONE 2013; V003T06A014https://doi.org/10.1115/ICONE21-15361

Abstract

View Articletitled, Sensitivity Studies on the Influence of Shutdown Control Assembly Banks Arrangement in Rod Control Assembly Banks Withdrawal From a Subcritical Condition

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Topics: Manufacturing , Power stations , Accidents , Computational methods , Enthalpy , Thermal energy , Transients (Dynamics)

Research on Fault Diagnosis Approach Based on the Signed Directed Graph Model for Nuclear Power Plant

Zhen Liu, Yong-kuo Liu, Xiao-tian Wu, Xian Zeng

ICONE 2013; V003T06A015https://doi.org/10.1115/ICONE21-15437

Abstract

View Articletitled, Research on Fault Diagnosis Approach Based on the Signed Directed Graph Model for Nuclear Power Plant

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Topics: Fault diagnosis , Nuclear power stations

Numerical Simulation of Electromagnetic Field in the Cold Crucible

Jinlong Zhang, Pengfei Li

ICONE 2013; V003T06A016https://doi.org/10.1115/ICONE21-15449

Abstract

View Articletitled, Numerical Simulation of Electromagnetic Field in the Cold Crucible

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Topics: Computer simulation , Electromagnetic fields , Heat , Joules , Heat transfer , Electromagnetic force , Electromagnetic induction , Heating , Cooling , Energy efficiency

Improvement on Dual Energy CT Reconstruction Method With Reduced Data

Yuanyuan Liu, Peng Zheng, Chunming Zhang

ICONE 2013; V003T06A017https://doi.org/10.1115/ICONE21-15462

Abstract

View Articletitled, Improvement on Dual Energy CT Reconstruction Method With Reduced Data

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Topics: Computer simulation , Errors , Inspection , Safety , Security , Sensors

Heat Sink Issue: A Specific Safety Issue for NPP Site Selection and Evaluation in the Warm Countries With Extreme Climatic Conditions

Andrei Rodionov, Jean-Marie Mattei

ICONE 2013; V003T06A018https://doi.org/10.1115/ICONE21-15529

Abstract

View Articletitled, Heat Sink Issue: A Specific Safety Issue for NPP Site Selection and Evaluation in the Warm Countries With Extreme Climatic Conditions

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Topics: Heat sinks , Nuclear power stations , Safety

TRACE Validation Against LOCA Transients Performed on FIX-II Facility

Xiao Hu, Mian Xing, Weimin Ma

ICONE 2013; V003T06A019https://doi.org/10.1115/ICONE21-15553

Abstract

View Articletitled, TRACE Validation Against LOCA Transients Performed on FIX-II Facility

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Topics: Safety , Transients (Dynamics)

Spent Fuel Pool Accidents in a Nordic BWR

Niina E. Könönen

ICONE 2013; V003T06A020https://doi.org/10.1115/ICONE21-15641

Abstract

View Articletitled, Spent Fuel Pool Accidents in a Nordic BWR

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Topics: Accidents , Boiling water reactors , Spent nuclear fuels , Fuels , Cooling , Floods , Temperature , Air flow , Cladding systems (Building) , Coolants

Simulation on the Decontamination Efficiency and Factor of Radioactive Waste Water Disposed by Supersonic Wave

Guangxia Zuo, Bin He, Rusong Li, Fengmei Yu, Wenyan Ma

ICONE 2013; V003T06A021https://doi.org/10.1115/ICONE21-15670

Abstract

View Articletitled, Simulation on the Decontamination Efficiency and Factor of Radioactive Waste Water Disposed by Supersonic Wave

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Topics: Decontamination , Radioactive wastes , Simulation , Water , Waves

Preliminary Study on the Primary Side Structure Design Improvement Based on CPR1000

Jianshu Lin, Chengjun Zhuang, Jun Cui, Ting Wang, Zhenhua Zhang

ICONE 2013; V003T06A022https://doi.org/10.1115/ICONE21-15687

Abstract

View Articletitled, Preliminary Study on the Primary Side Structure Design Improvement Based on CPR1000

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Topics: Design , Vessels , Fuel rods , Water , Accidents , Nuclear design , Power uprate , Probability , Safety , Temperature

Characteristic Analysis of Supercritical Water-Cooled Reactor During Uncontrolled CR Withdrawal at Normal Operation Transient

Wanxu Cheng, Tao Zhou, Liang Liu, Mingqiang Song, Bangyang Xia

ICONE 2013; V003T06A023https://doi.org/10.1115/ICONE21-15774

Abstract

View Articletitled, Characteristic Analysis of Supercritical Water-Cooled Reactor During Uncontrolled CR Withdrawal at Normal Operation Transient

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Topics: Cladding systems (Building) , Temperature , Transients (Dynamics) , Water , Feedback , Coolants , Density , Flow (Dynamics) , Pressure , Steam

3-D Base Control Systems for the Seismic Protection of Power Plant Equipment and Buildings

Peter Nawrotzki, Weiqiang Wang

ICONE 2013; V003T06A024https://doi.org/10.1115/ICONE21-15814

Abstract

View Articletitled, 3-D Base Control Systems for the Seismic Protection of Power Plant Equipment and Buildings

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Topics: Control systems , Power stations , Structures , Nuclear power stations , Safety , Damage , Earthquakes , Machinery , Aircraft , Dampers

An Implementation of DFM for Reliability Modeling and Analyzing of AP1000 FWCS

Jiubo Yin, Jianyuan Cao, Xu Wang

ICONE 2013; V003T06A025https://doi.org/10.1115/ICONE21-15828

Abstract

View Articletitled, An Implementation of DFM for Reliability Modeling and Analyzing of AP1000 FWCS

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Topics: Design for Manufacturing , Failure mode and effects analysis , Modeling , Reliability

An Investigation of Deterministic Realistic Method for LBLOCA Mass and Energy Release Evaluation for CPR1000 NPPs

Jianshu Lin, Chengjun Zhuang, Jinzhen Leng, Ting Wang, Zhenhua Zhang

ICONE 2013; V003T06A026https://doi.org/10.1115/ICONE21-15833

Abstract

View Articletitled, An Investigation of Deterministic Realistic Method for LBLOCA Mass and Energy Release Evaluation for CPR1000 NPPs

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Topics: Nuclear power stations , Containment , Design , Pressure , Safety

Fretting Wear Behavior of NC30Fe in Distilled Water and Hydrazine Solution

Hong Guo, Pengdi Ren, Xiaoyu Zhang, Guangxiong Chen, Yi Ye

ICONE 2013; V003T06A027https://doi.org/10.1115/ICONE21-15879

Abstract

View Articletitled, Fretting Wear Behavior of NC30Fe in Distilled Water and Hydrazine Solution

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Topics: Delamination , Water , Wear

Measurement of Gas Temperature in a Large Enclosure by Tunable Diode Laser Absorption Spectroscopy

Jun Tian, Zulong Hao, Yu Yu, Huagui Li, Jianjun He, Yilin Zhang, Jiayuan Li

ICONE 2013; V003T06A028https://doi.org/10.1115/ICONE21-15885

Abstract

View Articletitled, Measurement of Gas Temperature in a Large Enclosure by Tunable Diode Laser Absorption Spectroscopy

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Topics: Absorption , Absorption spectroscopy , Containment , Lasers , Temperature , Temperature measurement

Thermal-Hydraulic Simulations of Guard Containment in Depressurization Accidents of a Gas-Cooled Fast Reactor

Zhanjie Xu, Thomas Jordan

ICONE 2013; V003T06A029https://doi.org/10.1115/ICONE21-15955

Abstract

View Articletitled, Thermal-Hydraulic Simulations of Guard Containment in Depressurization Accidents of a Gas-Cooled Fast Reactor

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Topics: Accidents , Containment , Fast neutron reactors , Simulation , Design , Pressure , Boundary-value problems , Computational fluid dynamics , Helium , Nuclear reactors

A Review on Application of Technologies for Measuring Hydrogen Concentration in Containment

Sha Luo, Shaobo Wang, Liang Qin, Feng Pang

ICONE 2013; V003T06A030https://doi.org/10.1115/ICONE21-15965

Abstract

View Articletitled, A Review on Application of Technologies for Measuring Hydrogen Concentration in Containment

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Topics: Accidents , Containment , Hydrogen

The Analysis of AP1000 Depressurization During Small Break LOCA

Shuangji He

ICONE 2013; V003T06A031https://doi.org/10.1115/ICONE21-15968

Abstract

View Articletitled, The Analysis of AP1000 Depressurization During Small Break LOCA

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Topics: Compressibility , Failure , Fluids , Nuclear reactor coolants , Sensitivity analysis , Steam , Transients (Dynamics) , Valves , Water

Device for Measuring Hydrogen Concentration in Containment During Severe Accident

Sha Luo, Shaobo Wang, Liang Qin, Feng Pang

ICONE 2013; V003T06A032https://doi.org/10.1115/ICONE21-15970

Abstract

View Articletitled, Device for Measuring Hydrogen Concentration in Containment During Severe Accident

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Topics: Accidents , Containment , Hydrogen

Design of a Low Vulnerability Electronic Fiber Optic Seal System

Yuming Di, Quanhu Zhang, Guangxia Zuo, Feng Han, Ronghua Chen, Yonggang Huo, Peng Xu

ICONE 2013; V003T06A033https://doi.org/10.1115/ICONE21-15993

Abstract

View Articletitled, Design of a Low Vulnerability Electronic Fiber Optic Seal System

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Topics: Design , Fibers , Circuits , Encryption , Switches , Temperature , Calibration , Clocks , Data storage systems , Fault diagnosis

Analysis of Liquid Sloshing in an In-Containment Refueling Water Storage Tank for AP1000

Yu Liu, Daogang Lu, Junjie Dang, Licun Wu, Wenhui Ma

ICONE 2013; V003T06A034https://doi.org/10.1115/ICONE21-16007

Abstract

View Articletitled, Analysis of Liquid Sloshing in an In-Containment Refueling Water Storage Tank for AP1000

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Topics: Containment , Modal analysis , Sloshing , Water storage , Waves

The Development and Application of PWR Severe Accident Simulation Model

Yanfang Chen, Zhengquan Xie, Xusheng Lin, Fuchang Shan, Wei Wei, Fude Guo

ICONE 2013; V003T06A035https://doi.org/10.1115/ICONE21-16058

Abstract

View Articletitled, The Development and Application of PWR Severe Accident Simulation Model

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Topics: Accidents , Pressurized water reactors , Simulation models , Simulation , Engineers , Nuclear power stations , Safety

A Comparison in the Accuracy of Mapping Nuclear Fallout Patterns Using DELFIC and Several Modified Models Based on DELFIC

Jian-bo Shang, Quan-lin Shi, Qun-shu Wang

ICONE 2013; V003T06A036https://doi.org/10.1115/ICONE21-16092

Abstract

View Articletitled, A Comparison in the Accuracy of Mapping Nuclear Fallout Patterns Using DELFIC and Several Modified Models Based on DELFIC

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Topics: Computation , Computer software , Defense industry , DNA , Explosions , Hazards , Particulate matter , Semiconductor wafers , Trajectories (Physics) , Vortices

Safety Analysis on Mitigation Overpressure ATWS in VVER-1000 NPP

Ting Qi, Changjiang Yang

ICONE 2013; V003T06A037https://doi.org/10.1115/ICONE21-16165

Abstract

View Articletitled, Safety Analysis on Mitigation Overpressure ATWS in VVER-1000 NPP

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Topics: Nuclear power stations , Safety , Thermal hydraulics , Transients (Dynamics)

CFD Analysis on Hydrogen Risk in Subcompartment of the Containment

Zhiqiang Zou, Jian Deng, Yu Zhang

ICONE 2013; V003T06A038https://doi.org/10.1115/ICONE21-16171

Abstract

View Articletitled, CFD Analysis on Hydrogen Risk in Subcompartment of the Containment

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Topics: Computational fluid dynamics , Containment , Hydrogen , Risk , Explosions , Accidents , Boilers , Combustion , Containment buildings , Flames

Application of Integrated Safety Assessment Methodology to Feed and Bleed Sequences

C. Queral, J. Mula, J. Gómez-Magán, J. Gil, I. Fernández, E. Meléndez, M. Sánchez-Perea, J. Hortal

ICONE 2013; V003T06A039https://doi.org/10.1115/ICONE21-16334

Abstract

View Articletitled, Application of Integrated Safety Assessment Methodology to Feed and Bleed Sequences

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Topics: Damage , Safety

Effects of Break Location and Time Uncertainties in Small-Break and Medium-Break LOCA Sequences With Unavailability of HPSI

J. Gonzalez-Cadelo, C. Queral, J. Montero-Mayorga

ICONE 2013; V003T06A040https://doi.org/10.1115/ICONE21-16348

Abstract

View Articletitled, Effects of Break Location and Time Uncertainties in Small-Break and Medium-Break LOCA Sequences With Unavailability of HPSI

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Topics: Uncertainty , Damage , Vessels , Accident management , Engineering simulation , Pressurized water reactors , Probabilistic safety assessment , Safety , Simulation

Damage Domains Calculation Associated With Multiple Damages in a Steam Generator Tube Rupture Dynamic Event Tree

Gonzalo Jimenez, Cesar Queral, Maria Jose Rebollo-Mena, Javier Magan, Ivan Fernandez, Jesus Gil, Miguel Sanchez-Perea, Jose Maria Izquierdo, Enrique Melendez, Javier Hortal

ICONE 2013; V003T06A041https://doi.org/10.1115/ICONE21-16369

Abstract

View Articletitled, Damage Domains Calculation Associated With Multiple Damages in a Steam Generator Tube Rupture Dynamic Event Tree

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Topics: Boilers , Damage , Rupture , Risk , Safety , Simulation , Pressurized water reactors

The Fault Tree Analysis on Auxiliary Feedwater Pump Room Ventilation System in Pressurized Water Reactor Power

Yang Li, Chen Hang

ICONE 2013; V003T06A042https://doi.org/10.1115/ICONE21-16398

Abstract

View Articletitled, The Fault Tree Analysis on Auxiliary Feedwater Pump Room Ventilation System in Pressurized Water Reactor Power

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Topics: Feedwater , Pressurized water reactors , Pumps , Ventilation , Accidents , Hazards , Design , HVAC equipment , Maintenance , Nuclear power

Experimental Study of Feed Water Level Decreasing Effect on VVER Steam Generator Model Operation in Condensation Mode

A. V. Morozov, O. V. Remizov, A. S. Soshkina

ICONE 2013; V003T06A043https://doi.org/10.1115/ICONE21-16470

Abstract

View Articletitled, Experimental Study of Feed Water Level Decreasing Effect on VVER Steam Generator Model Operation in Condensation Mode

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Topics: Boilers , Condensation , Feedwater , Accidents , Circuits , Steam , Test facilities , Cooling , Design , Heat

Experimental Investigation of CCFL in Large Diameter Hot-Leg Geometry

Suleiman Al Issa, Rafael Macián-Juan

ICONE 2013; V003T06A044https://doi.org/10.1115/ICONE21-16510

Abstract

View Articletitled, Experimental Investigation of CCFL in Large Diameter Hot-Leg Geometry

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Topics: Geometry , Water , Computational fluid dynamics , Pressurized water reactors , Colliders (Nuclear physics) , Safety , Accidents , Atmospheric pressure , Databases , Engineering systems and industry applications

A Post Accident Safety Analysis Report of the Fukushima Accident — Future Direction of Evacuation: Lessons Learned

Genn Saji

ICONE 2013; V003T06A045https://doi.org/10.1115/ICONE21-16526

Abstract

View Articletitled, A Post Accident Safety Analysis Report of the Fukushima Accident — Future Direction of Evacuation: Lessons Learned

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Topics: Accidents , Evacuations , Fukushima nuclear disaster, Japan, 2011 , Safety

Analysis of Isolation Condenser Behavior by TRACG Code

Yoshihiko Ishii, Naoyuki Nakadozono, Hitoshi Ochi

ICONE 2013; V003T06A046https://doi.org/10.1115/ICONE21-16671

Abstract

View Articletitled, Analysis of Isolation Condenser Behavior by TRACG Code

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Topics: Condensers (steam plant) , Accidents , Countermeasures , Fukushima nuclear disaster, Japan, 2011 , Nuclear power stations , Pressure , Reactor vessels , Transient heat transfer

Safety Evaluation of Nuclear Plant Fire Using CFD Analysis

Akihiro Matsuda, Takashi Ishibashi, Susumu Tsuchino

ICONE 2013; V003T06A047https://doi.org/10.1115/ICONE21-16683

Abstract

View Articletitled, Safety Evaluation of Nuclear Plant Fire Using CFD Analysis

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Topics: Computational fluid dynamics , Fire , Nuclear power stations , Safety , Cables , Temperature , Fire testing , Insulation , Computer simulation , Dynamics (Mechanics)

ALWR PRA Standard Development

James R. Chapman

ICONE 2013; V003T06A048https://doi.org/10.1115/ICONE21-16831

Abstract

View Articletitled, ALWR PRA Standard Development

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Topics: Fire , Floods , Risk management

Fire PRA Insights

James R. Chapman

ICONE 2013; V003T06A049https://doi.org/10.1115/ICONE21-16832

Abstract

View Articletitled, Fire PRA Insights

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Topics: Fire , Failure , Defense industry , Design , Accidents , Coolants , Diesel generators , Emergencies , Fire risk , Licensing

Risk Insights and Use Based on Fukushima Accident

James R. Chapman, K. Raymond Fine, C. Rick Grantom

ICONE 2013; V003T06A050https://doi.org/10.1115/ICONE21-16834

Abstract

View Articletitled, Risk Insights and Use Based on Fukushima Accident

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Topics: Fukushima nuclear disaster, Japan, 2011 , Risk , Design , Hazards , Cooling , Damage , Decision making , Defense industry , Earthquake risk , Floods

Codes, Standards, Licensing and Regulatory Issues

Preliminary Research on the Elimination of OBE in the Seismic Design of NPP

Qiang Li, Jian Zhang

ICONE 2013; V003T07A001https://doi.org/10.1115/ICONE21-15064

Abstract

View Articletitled, Preliminary Research on the Elimination of OBE in the Seismic Design of NPP

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Topics: Earthquake resistant design , Nuclear power stations

Codes Comparison and Analysis of Weld Cladding Ultrasonic Testing in Nuclear Power Plants

Zhimin Zhong, Jian Min, Kai Li

ICONE 2013; V003T07A002https://doi.org/10.1115/ICONE21-15086

Abstract

View Articletitled, Codes Comparison and Analysis of Weld Cladding Ultrasonic Testing in Nuclear Power Plants

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Topics: Cladding systems (Building) , Nuclear power stations , Ultrasonic testing , Inspection , China , ASME Boiler and Pressure Vessel Code , Nondestructive evaluation , Nuclear power , Pipes , Pressure vessels

Historical Perspectives and Insights on ACRS Review of AP1000 Design Certification

Hossein Nourbakhsh, Weidong Wang, Harold Ray, Thomas Kress

ICONE 2013; V003T07A003https://doi.org/10.1115/ICONE21-15176

Abstract

View Articletitled, Historical Perspectives and Insights on ACRS Review of AP1000 Design Certification

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Topics: Design , Safety

A Study of Rules of Material Groupings in ASME IX QW-420 by Decision Tree Method

Lifeng Guo, Yaochun Zhang, Libo Shi, An Dong

ICONE 2013; V003T07A004https://doi.org/10.1115/ICONE21-15291

Abstract

View Articletitled, A Study of Rules of Material Groupings in ASME IX QW-420 by Decision Tree Method

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Topics: ASME Standards , Base metals , Heat treating (Metalworking) , Mechanical properties , Strategic materials , Welding , Welding operators

Proposed Improvements of the ASME B&PV Code and Future Directions of CIWG

Jinquan Yan, Yinbiao He, Gang Li, Hao Yu

ICONE 2013; V003T07A005https://doi.org/10.1115/ICONE21-15404

Abstract

View Articletitled, Proposed Improvements of the ASME B&PV Code and Future Directions of CIWG

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Topics: Acceptance criteria , ASME Standards , China , Construction , Design , Fatigue , Hydrostatic testing , Nuclear industry , Nuclear power stations , Power stations

Study and Compare on Classification and Management Requirements of Domestic and Foreign Research Reactors

Haiyang Wang, Chenxiu Song, Quanyuan Gao

ICONE 2013; V003T07A006https://doi.org/10.1115/ICONE21-15412

Abstract

View Articletitled, Study and Compare on Classification and Management Requirements of Domestic and Foreign Research Reactors

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Topics: China , Fukushima nuclear disaster, Japan, 2011 , Governments , Inspection , Nuclear power , Nuclear reactor accidents , Regulations , Safety

Comparison of PTS Guides for Reactor Pressure Vessel Integrity Assessment

Milan Brumovsky

ICONE 2013; V003T07A007https://doi.org/10.1115/ICONE21-15419

Abstract

View Articletitled, Comparison of PTS Guides for Reactor Pressure Vessel Integrity Assessment

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Topics: Reactor vessels , Fracture mechanics , ASME Standards , Cooling , Emergencies , Materials degradation , Materials properties , Nuclear power stations , Safety , Testing

Lessons Learned From Automation of Nonconformance Reporting (NCR) Process at Los Alamos National Laboratory (LANL)

Shyla A. McFarland, Taunia S. Van Valkenburg, Gary M. Sandquist, Daniel J. Tepley, Ernie F. Petru

ICONE 2013; V003T07A008https://doi.org/10.1115/ICONE21-15439

Abstract

View Articletitled, Lessons Learned From Automation of Nonconformance Reporting (NCR) Process at Los Alamos National Laboratory (LANL)

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Topics: Project management , Quality control

Consideration on Selection of Design Codes and Standards for China Fusion Engineering Testing Reactor

Guoqing Li, Chao Xing, Yexi Kang, Xiaozhen Li

ICONE 2013; V003T07A009https://doi.org/10.1115/ICONE21-15476

Abstract

View Articletitled, Consideration on Selection of Design Codes and Standards for China Fusion Engineering Testing Reactor

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Topics: China , Design , Engineering standards , Testing , Magnetic fusion , Nuclear industry , Construction , Cycles , In-service inspection , Mechanical engineers

Quality Assurance for a Nuclear Power Plant Simulator by Applying Standards for Safety-Critical Software

Cheng Ye, Chao Ni, Tian Zheng, Zhicheng Zhang, Ronghua Zhang

ICONE 2013; V003T07A010https://doi.org/10.1115/ICONE21-15488

Abstract

View Articletitled, Quality Assurance for a Nuclear Power Plant Simulator by Applying Standards for Safety-Critical Software

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Topics: Computer software , Nuclear power stations , Quality control , Safety , Life cycle assessment

Comparison of Different Acceptance Standard for Radiographic Rounded Indications in Welds

Cong Wang, GuoXiang Tang, JiaGuan Zhao, HengLiang Yang

ICONE 2013; V003T07A011https://doi.org/10.1115/ICONE21-15491

Abstract

View Articletitled, Comparison of Different Acceptance Standard for Radiographic Rounded Indications in Welds

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Topics: Acceptance criteria , ASME Boiler and Pressure Vessel Code , Testing , Welded joints

Exploration of China Nuclear Power Standard System Development

Jinquan Yan, Shenjie Gu, Lin Tian

ICONE 2013; V003T07A012https://doi.org/10.1115/ICONE21-15551

Abstract

View Articletitled, Exploration of China Nuclear Power Standard System Development

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Topics: China , Nuclear industry , Nuclear power

Inspection Qualification of Ultrasonic Inspection for RPV Safe End Narrow Gap Welding With Visualization of Laser Ultrasonic Detection Technology and Computerized Ultrasonic Simulation

ShuXian Yuan, Ming Li, GuanBing Ma, XueZhu Xiao, TianMing Lv

ICONE 2013; V003T07A013https://doi.org/10.1115/ICONE21-15591

Abstract

View Articletitled, Inspection Qualification of Ultrasonic Inspection for RPV Safe End Narrow Gap Welding With Visualization of Laser Ultrasonic Detection Technology and Computerized Ultrasonic Simulation

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Topics: Inspection , Lasers , Simulation , Visualization , Welding , Welded joints , Casting , China , Forging , Nuclear power stations

Application of RSE-M2010 on In-Service Inspection of Taishan EPR Project

Xueliang Zhang, Chunbing Shao, Ximing Tang, Cheng Yang, Huixing Feng

ICONE 2013; V003T07A014https://doi.org/10.1115/ICONE21-15842

Abstract

View Articletitled, Application of RSE-M2010 on In-Service Inspection of Taishan EPR Project

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Topics: In-service inspection

Study on the Nonradioactive Environmental Impact Assessments for Chinese Nuclear Power Plants

Xinyu Wei, Hongbin Ma, Xiaowei Xiong, Duanjie Yang, Zhaorong Shang

ICONE 2013; V003T07A015https://doi.org/10.1115/ICONE21-16121

Abstract

View Articletitled, Study on the Nonradioactive Environmental Impact Assessments for Chinese Nuclear Power Plants

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Topics: Nuclear power stations , China , Emissions , Hazardous wastes , Radiation (Physics) , Regulations , Statistics

Nuclear Power Plant Design Verification Based on the Analyzer

Hanlin Wang, Mingguang Zheng, Tunfeng Qi

ICONE 2013; V003T07A016https://doi.org/10.1115/ICONE21-16372

Abstract

View Articletitled, Nuclear Power Plant Design Verification Based on the Analyzer

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Topics: Nuclear design , Design , Nuclear power stations

RCC-M and RSE-M: A Set of Consistent Codes for PWR Design and Operation

Claude Faidy

ICONE 2013; V003T07A017https://doi.org/10.1115/ICONE21-16375

Abstract

View Articletitled, RCC-M and RSE-M: A Set of Consistent Codes for PWR Design and Operation

PDF

Topics: Design , Pressurized water reactors , Surveillance , Construction , Inspection , Maintenance , Manufacturing , Nuclear power stations , Welding

Major Improvements of French Mechanical Nuclear Components Codes: RCC-M, RCC-MRx and RSE-M

Claude Faidy

ICONE 2013; V003T07A018https://doi.org/10.1115/ICONE21-16376

Abstract

View Articletitled, Major Improvements of French Mechanical Nuclear Components Codes: RCC-M, RCC-MRx and RSE-M

PDF

Topics: Construction , Design , Fusion reactors , High temperature , Nuclear power stations , Pressure , Pressurized water reactors , Surveillance

Fatigue of Stainless Steel Components: Toward Codified Rules Improvements

Claude Faidy

ICONE 2013; V003T07A019https://doi.org/10.1115/ICONE21-16379

Abstract

View Articletitled, Fatigue of Stainless Steel Components: Toward Codified Rules Improvements

PDF

Topics: Fatigue , Stainless steel , Pressurized water reactors , Fatigue analysis , Fatigue cracks , Fatigue testing , High cycle fatigue

Selection of Chemical Hazard Prediction Models for Plant Safety and Control Room Habitability Evaluations

Mary C. Richmond, Ping K. Wan, Brady P. Dague, Kyra W. Davis

ICONE 2013; V003T07A020https://doi.org/10.1115/ICONE21-16392

Abstract

View Articletitled, Selection of Chemical Hazard Prediction Models for Plant Safety and Control Room Habitability Evaluations

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Topics: Control rooms , Hazards , Safety , Accidents , Damage , Design , Explosions , Fire , Nuclear power stations , Chemical properties

Water Use Management Challenges in Power Generation

Kit Y. Ng, Ping K. Wan

ICONE 2013; V003T07A021https://doi.org/10.1115/ICONE21-16393

Abstract

View Articletitled, Water Use Management Challenges in Power Generation

PDF

Topics: Cooling , Energy generation , Nuclear power stations , Water

Off-Site Emergency Response of AP1000

Xiaodong Huang, Fenglei Du

ICONE 2013; V003T07A022https://doi.org/10.1115/ICONE21-16718

Abstract

View Articletitled, Off-Site Emergency Response of AP1000

PDF

Topics: Accidents , China , Emergencies , Emergency management , Emergency response , Evacuations , Fukushima nuclear disaster, Japan, 2011 , Nuclear power stations , Regulations

Towards the Development of Shutdown Emergency Operating Procedures for Power Nuclear Reactors

Isaac Malgas

ICONE 2013; V003T07A023https://doi.org/10.1115/ICONE21-16788

Abstract

View Articletitled, Towards the Development of Shutdown Emergency Operating Procedures for Power Nuclear Reactors

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Topics: Emergencies , Nuclear reactors , Accidents , Nuclear reactor coolants , Design , Boilers , Bridges (Structures) , Heat , Licensing , Nuclear power stations

More on Design Evaluation of Nuclear Power Piping Subjected to Time-History Dynamic Loads According to ASME B&PV III

Lingfu Zeng, Lennart G. Jansson

ICONE 2013; V003T07A024https://doi.org/10.1115/ICONE21-16792

Abstract

View Articletitled, More on Design Evaluation of Nuclear Power Piping Subjected to Time-History Dynamic Loads According to ASME B&PV III

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Topics: Design , Nuclear power , Pipes , Stress , Finite element analysis , Piping systems , Plasticity , Transients (Dynamics) , Water hammer

An Introduction to RCC-C: An AFCEN Code for Design and Construction of PWR Fuel Assemblies

Christine Vauglin, Marc Ton-That, Morello Sperandio, Denis Buisine

ICONE 2013; V003T07A025https://doi.org/10.1115/ICONE21-16810

Abstract

View Articletitled, An Introduction to RCC-C: An AFCEN Code for Design and Construction of PWR Fuel Assemblies

PDF

Topics: Construction , Design , Fuels , Pressurized water reactors

Introduction to KEPIC (Korea Electric Power Industry Code)

Myoung-Sung Sohn, Hyun-Jae Joo, Hoon-Seok Byun, Jong-Hae Kim

ICONE 2013; V003T07A026https://doi.org/10.1115/ICONE21-16827

Abstract

View Articletitled, Introduction to KEPIC (Korea Electric Power Industry Code)

PDF

Topics: Electricity (Physics) , Engineering standards , Nuclear power stations , Construction , ASME Boiler and Pressure Vessel Code , Design , Welding , ASTM International , Concretes , Electric fields

Computational Fluid Dynamics and Coupled Codes

Analysis of Main Steam Line Break Accident at Hot Shutdown State Using a Coupled Method

Dawei Cui, Jinzhen Leng, Jun Chen

ICONE 2013; V003T10A001https://doi.org/10.1115/ICONE21-15007

Abstract

View Articletitled, Analysis of Main Steam Line Break Accident at Hot Shutdown State Using a Coupled Method

PDF

Topics: Accidents , Steam , Computers , Safety , Simulation , Thermal hydraulics , Transients (Dynamics)

A Study of GOTHIC 8.0 Code Application to AP1000 Containment Response

Guodong Wang, Zhe Wang

ICONE 2013; V003T10A002https://doi.org/10.1115/ICONE21-15014

Abstract

View Articletitled, A Study of GOTHIC 8.0 Code Application to AP1000 Containment Response

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Topics: Containment , Condensation , Evaporation , Heat , Mass transfer , Shells , Diffusion (Physics) , Exterior walls , Heat conduction , Heat transfer coefficients

The Design and CFD Simulation of a New Spent Fuel Pool Passive Cooling System

Cheng Ye, Minglu Wang, Mingguang Zheng, Zhengqin Xiong, Ronghua Zhang

ICONE 2013; V003T10A003https://doi.org/10.1115/ICONE21-15040

Abstract

View Articletitled, The Design and CFD Simulation of a New Spent Fuel Pool Passive Cooling System

PDF

Topics: Computational fluid dynamics , Cooling systems , Design , Heat pipes , Simulation , Spent nuclear fuels

Flow Characteristics of Fuel Bundle With New Mixing Vane Design

Wenchi Yu, Zhengzheng Pang, Yuemin Zhou, Weicai Li, Xiaoming Chen

ICONE 2013; V003T10A004https://doi.org/10.1115/ICONE21-15049

Abstract

View Articletitled, Flow Characteristics of Fuel Bundle With New Mixing Vane Design

PDF

Topics: Design , Flow (Dynamics) , Fuels

Development and Validation of Two-Way Fluid-Particle Coupling in Turbulent Flows for a CFD Code

Jianjun Xiao, Anatoly Svishchev, Thomas Jordan

ICONE 2013; V003T10A005https://doi.org/10.1115/ICONE21-15051

Abstract

View Articletitled, Development and Validation of Two-Way Fluid-Particle Coupling in Turbulent Flows for a CFD Code

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Topics: Computational fluid dynamics , Fluids , Particulate matter , Turbulence , Algorithms , Drops , Dynamics (Mechanics) , Gas flow , Momentum , Nozzles

Preliminary Analysis of Two-Phase Flow in a Steam Generator Using CUPID-SG

Hyungrae Kim, Soo Hyoung Kim, Seung-Jun Lee, Ik Kyu Park, Han Young Yoon

ICONE 2013; V003T10A006https://doi.org/10.1115/ICONE21-15124

Abstract

View Articletitled, Preliminary Analysis of Two-Phase Flow in a Steam Generator Using CUPID-SG

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Topics: Boilers , Two-phase flow , Constitutive equations , Heat , Boiling , Computers , Drag (Fluid dynamics) , Flow (Dynamics) , Fluids , Friction

Numerical Investigation of Two Phase Flow and Heat Transfer Characteristics of Passive Containment Cooling System

Jia-Jia Deng, Liang-Ming Pan, Mei-Qiang Kang

ICONE 2013; V003T10A007https://doi.org/10.1115/ICONE21-15128

Abstract

View Articletitled, Numerical Investigation of Two Phase Flow and Heat Transfer Characteristics of Passive Containment Cooling System

PDF

Topics: Containment , Cooling systems , Heat transfer , Two-phase flow , Water , Flow (Dynamics) , Natural convection , Accidents , Air flow , Computational fluid dynamics

Experimental Analyses by SIMMER-III on Duct-Wall Failure and Fuel Discharge/Relocation Behavior

Hidemasa Yamano, Yoshiharu Tobita

ICONE 2013; V003T10A008https://doi.org/10.1115/ICONE21-15163

Abstract

View Articletitled, Experimental Analyses by SIMMER-III on Duct-Wall Failure and Fuel Discharge/Relocation Behavior

PDF

Topics: Ducts , Experimental analysis , Failure , Fuels , Coolants , Accidents , Boiling , Computers , Fluid dynamics , Melting

Fluid-Structure Coupling Analysis for the Flow Distribution Device of Nuclear Reactor Internals

Mingqian Zhang, Yuangang Duan, Xiaobing Ran, Yanwu Liu

ICONE 2013; V003T10A009https://doi.org/10.1115/ICONE21-15180

Abstract

View Articletitled, Fluid-Structure Coupling Analysis for the Flow Distribution Device of Nuclear Reactor Internals

PDF

Topics: Flow (Dynamics) , Fluids , Nuclear reactors , Computational fluid dynamics , Fluid dynamics , Fluid structure interaction , Pressure , Pressurized water reactors , Reactor vessels , Stress

Conservative Front-Tracking Method for 2-Dimensional Deformable Drops

Lei Chang, Yanning Yang

ICONE 2013; V003T10A010https://doi.org/10.1115/ICONE21-15187

Abstract

View Articletitled, Conservative Front-Tracking Method for 2-Dimensional Deformable Drops

PDF

Topics: Computer simulation , Computers , Finite difference methods , Fluids , Momentum , Simulation results , Temperature distribution

Numerical Study on the Influence of Non-Uniform Wall Roughness on Vortex Structure in Sparse Lattice

Hongguang Xiao, Yangwei Zhang, Binghuo Yan, Wenzhen Chen

ICONE 2013; V003T10A011https://doi.org/10.1115/ICONE21-15194

Abstract

View Articletitled, Numerical Study on the Influence of Non-Uniform Wall Roughness on Vortex Structure in Sparse Lattice

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Topics: Surface roughness , Vortices , Heat transfer , Flow (Dynamics) , Simulation , Stress

Development and Application of Single-Phase CFD Methodology for Estimating Flow Field in Rod Bundles

Fujun Gan, Libing Zhu, Jiazheng Liu, Yixiong Zheng, Xing Tong

ICONE 2013; V003T10A012https://doi.org/10.1115/ICONE21-15198

Abstract

View Articletitled, Development and Application of Single-Phase CFD Methodology for Estimating Flow Field in Rod Bundles

PDF

Topics: Computational fluid dynamics , Flow (Dynamics) , Fuel rods , Design , Simulation , Turbulence , Computer software , Fuels , Manufacturing , Nuclear engineering

Numerical Simulation of Quasi Periodic Large Scale Vortices in Rod Bundles With Non-Uniform Wall Roughness

Gaojie Hu, Lei Yu, Yangwei Zhang, Binghuo Yan

ICONE 2013; V003T10A013https://doi.org/10.1115/ICONE21-15202

Abstract

View Articletitled, Numerical Simulation of Quasi Periodic Large Scale Vortices in Rod Bundles With Non-Uniform Wall Roughness

PDF

Topics: Computer simulation , Fuel rods , Surface roughness , Vortices , Flow (Dynamics) , Heat transfer , Turbulence , Design , Simulation , Stress

Analysis of the Thermal Hydraulic Phenomena Caused by Steam Jets in AP1000 Containment

Yingqiu Hu, Yu Yu, Fenglei Niu, Xin Liu, Ruichang Zhao

ICONE 2013; V003T10A014https://doi.org/10.1115/ICONE21-15226

Abstract

View Articletitled, Analysis of the Thermal Hydraulic Phenomena Caused by Steam Jets in AP1000 Containment

PDF

Topics: Containment , Jets , Steam , Design , Fluids , Heat , Mass transfer , Simulation , Space , Temperature

Multiphase Flow Simulation of Subcooled Boiling Using the N-Phase Approach in TransAT

S. Thomas, C. Narayanan, D. Lakehal, Y. Gong

ICONE 2013; V003T10A015https://doi.org/10.1115/ICONE21-15339

Abstract

View Articletitled, Multiphase Flow Simulation of Subcooled Boiling Using the N-Phase Approach in TransAT

PDF

Topics: Boiling , Multiphase flow , Simulation , Subcooling , Modeling , Pressurized water reactors , Temperature , Pressure , Reynolds-averaged Navier–Stokes equations , Superheating

Departure From Nucleate Boiling Modeling Development for PWR Fuel

Jin Yan, L. David Smith, III, Zeses Karoutas

ICONE 2013; V003T10A016https://doi.org/10.1115/ICONE21-15345

Abstract

View Articletitled, Departure From Nucleate Boiling Modeling Development for PWR Fuel

PDF

Topics: Fuels , Modeling , Nucleate boiling , Pressurized water reactors , Computational fluid dynamics , Flow (Dynamics) , Boiling , Fuel rods , Light water reactors , Accidents

Thermal Hydraulics Numerical Simulation and Optimized Design of Passive Residual Heat Removal Heat Exchanger in AP1000

Huining Xia, Daogang Lu, Zheng Du, Yuhao Zhang, Xiaoliang Fu, Zhongying Ma, Yanhua Yang, Min Liang

ICONE 2013; V003T10A017https://doi.org/10.1115/ICONE21-15480

Abstract

View Articletitled, Thermal Hydraulics Numerical Simulation and Optimized Design of Passive Residual Heat Removal Heat Exchanger in AP1000

PDF

Topics: Computer simulation , Design , Heat , Heat exchangers , Thermal hydraulics , Heat transfer , Temperature , Fluids , Boiling , Containment

Thermal Hydraulics Analysis on a Simplified Model of Spent Fuel Pool

Min Liang, Daogang Lu, Huining Xia, Yuhao Zhang

ICONE 2013; V003T10A018https://doi.org/10.1115/ICONE21-15482

Abstract

View Articletitled, Thermal Hydraulics Analysis on a Simplified Model of Spent Fuel Pool

PDF

Topics: Spent nuclear fuels , Thermal hydraulics , Computer software , Water , Cooling , Safety , Accidents , Boiling , China , Computational fluid dynamics

Numerical Simulation of Self-Leveling Behavior in Debris Bed by a Hybrid Method

Liancheng Guo, Koji Morita, Hirotaka Tagami, Yoshiharu Tobita

ICONE 2013; V003T10A019https://doi.org/10.1115/ICONE21-15483

Abstract

View Articletitled, Numerical Simulation of Self-Leveling Behavior in Debris Bed by a Hybrid Method

PDF

Topics: Computer simulation , Particulate matter , Discrete element methods , Fast neutron reactors , Fluid dynamics , Fluids , Safety , Accidents , Algorithms , Flow (Dynamics)

Computational Simulation of Turbulent Natural Convection in a Volumetrically Heated Square Cavity

Camila Braga Vieira, Bojan Niceno, Jian Su

ICONE 2013; V003T10A020https://doi.org/10.1115/ICONE21-15486

Abstract

View Articletitled, Computational Simulation of Turbulent Natural Convection in a Volumetrically Heated Square Cavity

PDF

Topics: Cavities , Natural convection , Simulation , Turbulence , Computational fluid dynamics , Computer simulation , Fluids , Modeling , Navier-Stokes equations , Performance

Development of PCCSAP-3D Code for Passive Containment: Models of Noncondensable Gases, Aerosols and Fission Products

Ran Li, Jiyang Yu

ICONE 2013; V003T10A021https://doi.org/10.1115/ICONE21-15606

Abstract

View Articletitled, Development of PCCSAP-3D Code for Passive Containment: Models of Noncondensable Gases, Aerosols and Fission Products

PDF

Topics: Aerosols , Containment , Gases , Nuclear fission , Radioactivity , Accidents , Design , Hydrogen , Sprays , Boundary-value problems

Numerical Research on Performance of AP1000 Passive Containment Cooling System Without Falling Film

Hui Wang, Qiang Guo, Qiaoyan Chen

ICONE 2013; V003T10A022https://doi.org/10.1115/ICONE21-15644

Abstract

View Articletitled, Numerical Research on Performance of AP1000 Passive Containment Cooling System Without Falling Film

PDF

Topics: Containment , Cooling systems , Heat , Temperature , Natural convection , Thermal radiation , Flow (Dynamics) , Steel , Accidents , Computational fluid dynamics

Computational Study on a Single Flow Element in a Nuclear Thermal Rocket

Xiang Zhao, Trent Montgomery, Sijun Zhang

ICONE 2013; V003T10A023https://doi.org/10.1115/ICONE21-15683

Abstract

View Articletitled, Computational Study on a Single Flow Element in a Nuclear Thermal Rocket

PDF

Topics: Flow (Dynamics) , Rockets

The Effect of Electromagnetic Field on the Behavior of Bubbles

Hong-bo Liu, Liang-ming Pan

ICONE 2013; V003T10A024https://doi.org/10.1115/ICONE21-15689

Abstract

View Articletitled, The Effect of Electromagnetic Field on the Behavior of Bubbles

PDF

Topics: Bubbles , Electromagnetic fields , Magnetohydrodynamics

CFD Analysis of Thermal Stratification Phenomena in the RNS Suction Line of a Gen-III Nuclear Power Plant

Yan Li, Daogang Lu, Zhigang Wang, Jian Wu, Fengyun Yu

ICONE 2013; V003T10A025https://doi.org/10.1115/ICONE21-15735

Abstract

View Articletitled, CFD Analysis of Thermal Stratification Phenomena in the RNS Suction Line of a Gen-III Nuclear Power Plant

PDF

Topics: Computational fluid dynamics , Nuclear power stations , Suction , Thermal stratification , Leakage , Temperature , Flow (Dynamics) , Pipes , Density , Heat

The Research of the Fluid-Solid Interaction of the Passive Containment Cooling Tank and Shield Building Structure With Seismic Load in AP1000

Junjie Dang, Daogang Lu, Wenhui Ma, Yu Liu, Yang Hong

ICONE 2013; V003T10A026https://doi.org/10.1115/ICONE21-15778

Abstract

View Articletitled, The Research of the Fluid-Solid Interaction of the Passive Containment Cooling Tank and Shield Building Structure With Seismic Load in AP1000

PDF

Topics: Containment , Cooling , Cooling systems , Fluids , Stress

Study of Mixing Characteristics Over a Spacer Grid With Sloping Channels Based on Numerical Simulations in a PWR 5×5 Rod Bundle Using CFD Codes

Xi Chen, Hong Zhang

ICONE 2013; V003T10A027https://doi.org/10.1115/ICONE21-15795

Abstract

View Articletitled, Study of Mixing Characteristics Over a Spacer Grid With Sloping Channels Based on Numerical Simulations in a PWR 5×5 Rod Bundle Using CFD Codes

PDF

Topics: Computational fluid dynamics , Computer simulation , Fuel rods , Pressurized water reactors , Cross-flow , Fluids , Fuels , Heat transfer , Mesh generation , Pressure

Numerical Simulation Analysis on the Flow Mechanism of Passive Containment Cooling System

Yang Song, Wei-Hua Li, Sheng-Qiang Li

ICONE 2013; V003T10A028https://doi.org/10.1115/ICONE21-15818

Abstract

View Articletitled, Numerical Simulation Analysis on the Flow Mechanism of Passive Containment Cooling System

PDF

Topics: Computer simulation , Containment , Cooling systems , Flow (Dynamics) , Steam , Accidents , Pressure , Blasting , Computational fluid dynamics , Cooling

Numerical Investigation of Flow and Heat Transfer Characteristics in Wire-Wrap Tight Lattice 19-Rod Bundle

Minggang Li, Jun Wang, Changhua Nie, Xiao Yan, Yanping Huang, Zumao Yang, Feng Xie

ICONE 2013; V003T10A029https://doi.org/10.1115/ICONE21-15832

Abstract

View Articletitled, Numerical Investigation of Flow and Heat Transfer Characteristics in Wire-Wrap Tight Lattice 19-Rod Bundle

PDF

Topics: Flow (Dynamics) , Heat transfer , Wire , Fuel rods , Friction , Turbulence , Eddies (Fluid dynamics) , Viscosity , Computational fluid dynamics , Corners (Structural elements)

Two-Way Coupling Simulation of Heat Transfer in ADS Windowless Spallation Target

Jie Liu, Lei Gao, Huan Chen, Zeng-hui Wang, Wen-qiang Lu

ICONE 2013; V003T10A030https://doi.org/10.1115/ICONE21-15903

Abstract

View Articletitled, Two-Way Coupling Simulation of Heat Transfer in ADS Windowless Spallation Target

PDF

Topics: Computational fluid dynamics , Heat transfer , Nuclear physics , Simulation , Spallation (Nuclear physics)

CFD Analysis of Circumferential Temperature Distribution on Fuel Cladding Surface of China Lead Alloy Cooled Research Reactor (CLEAR-I)

Zhao Chen, Guangming Zhou, Tao Zhou, Hongli Chen, Yunqing Bai

ICONE 2013; V003T10A031https://doi.org/10.1115/ICONE21-15917

Abstract

View Articletitled, CFD Analysis of Circumferential Temperature Distribution on Fuel Cladding Surface of China Lead Alloy Cooled Research Reactor (CLEAR-I)

PDF

Topics: China , Cladding systems (Building) , Computational fluid dynamics , Fuels , Lead alloys , Temperature distribution

Study on the Flow Distribution at the Core Inlet

Mao Tang, Liang Chen, Yanwu Liu, Mingqian Zhang, Xiaolei Yu

ICONE 2013; V003T10A032https://doi.org/10.1115/ICONE21-15929

Abstract

View Articletitled, Study on the Flow Distribution at the Core Inlet

PDF

Topics: Flow (Dynamics) , Pressurized water reactors

Local Mesh Refinement for Viscid Flow in Combustion Code COM3D

Ke Ren, Alexei Kotchourko, Alexander Lelyakin

ICONE 2013; V003T10A033https://doi.org/10.1115/ICONE21-15930

Abstract

View Articletitled, Local Mesh Refinement for Viscid Flow in Combustion Code COM3D

PDF

Topics: Combustion , Flow (Dynamics) , Interpolation , Simulation , Diffusion (Physics) , Explosions , Turbulence

Three-Dimension Thermal Hydraulic Analysis of Stationary Target Plate for Highly Intensified Neutron Generator (HINEG)

Shuzhou Li, Hongli Chen, Tao Zhou, Fengquan Song, Wen Wang

ICONE 2013; V003T10A034https://doi.org/10.1115/ICONE21-16113

Abstract

View Articletitled, Three-Dimension Thermal Hydraulic Analysis of Stationary Target Plate for Highly Intensified Neutron Generator (HINEG)

PDF

Topics: Dimensions , Neutron generators , Computer software , Temperature , Computational fluid dynamics , Cooling , Design , Flow (Dynamics) , Fluids , Heat flux

Numerical Simulation of Supercritical Water Heat Transfer in the Vertically Heated Tube

Feng Wang, Bo Cui, Shijun Zhang, Xue Qin

ICONE 2013; V003T10A035https://doi.org/10.1115/ICONE21-16158

Abstract

View Articletitled, Numerical Simulation of Supercritical Water Heat Transfer in the Vertically Heated Tube

PDF

Topics: Computer simulation , Heat transfer , Water , Flux (Metallurgy) , Heat , Heat transfer coefficients , Turbulence , Computational fluid dynamics , Computer software , Heat flux

Full Implicit Integrate Solution to the Coupled Neutronics/Thermal-Hydraulics Problems

Han Zhang, Fu Li

ICONE 2013; V003T10A036https://doi.org/10.1115/ICONE21-16159

Abstract

View Articletitled, Full Implicit Integrate Solution to the Coupled Neutronics/Thermal-Hydraulics Problems

PDF

Topics: Thermal hydraulics

Numerical Simulations and Experiments on Gaseous Flow and Heat Transfer in Multiple Narrow Channels in Transition Region

Yuming Chen, Christine Klein, Frederik Arbeiter, German Ibaceta

ICONE 2013; V003T10A037https://doi.org/10.1115/ICONE21-16172

Abstract

View Articletitled, Numerical Simulations and Experiments on Gaseous Flow and Heat Transfer in Multiple Narrow Channels in Transition Region

PDF

Topics: Computational fluid dynamics , Computer simulation , Databases , Engineering simulation , Flow (Dynamics) , Fusion reactors , Gas flow , Heat transfer , Helium , Irradiation (Radiation exposure)

Simulation of MHD Effects and Thermal Issues in the DCLL Blanket for ITER

Long Chen, Yue-Fei Du, Ming-Jiu Ni, Nian-Mei Zhang

ICONE 2013; V003T10A038https://doi.org/10.1115/ICONE21-16269

Abstract

View Articletitled, Simulation of MHD Effects and Thermal Issues in the DCLL Blanket for ITER

PDF

Topics: Magnetohydrodynamics , Simulation , Deformation , Finite element methods , Flow (Dynamics) , Fluids , Thermal stresses , Computational fluid dynamics , Coolants , Electric potential

CFD Simulation of Flashing Boiling Flow in the Containment Cooling Condensers (CCC) System of KERENA™ Reactor

Yixiang Liao, Dirk Lucas, Eckhard Krepper, Roland Rzehak

ICONE 2013; V003T10A039https://doi.org/10.1115/ICONE21-16290

Abstract

View Articletitled, CFD Simulation of Flashing Boiling Flow in the Containment Cooling Condensers (CCC) System of KERENA™ Reactor

PDF

Topics: Boiling , Computational fluid dynamics , Condensers (steam plant) , Containment , Cooling , Flashing , Flow (Dynamics) , Simulation , Bubbles , Evaporation

Analysis of Fluid-Induced Excitation Forces in Triangular Tube Arrays Based on the LES Method

Qing-lei Jiang, Ji-yun Zhou, Xian-yuan Wang

ICONE 2013; V003T10A040https://doi.org/10.1115/ICONE21-16312

Abstract

View Articletitled, Analysis of Fluid-Induced Excitation Forces in Triangular Tube Arrays Based on the LES Method

PDF

Topics: Excitation , Fluids , Turbulence , Lift (Fluid dynamics) , Random excitation , Computer simulation , Boilers , Flow-induced vibrations , Reliability , Spectra (Spectroscopy)

Numerical Simulation on 3D Flow in the Fuel Transfer Canal and Local Flow Field Analysis

Qiang Guo, Hui Wang

ICONE 2013; V003T10A041https://doi.org/10.1115/ICONE21-16341

Abstract

View Articletitled, Numerical Simulation on 3D Flow in the Fuel Transfer Canal and Local Flow Field Analysis

PDF

Topics: Canals , Computer simulation , Flow (Dynamics) , Fuels , Spent nuclear fuels , Computational fluid dynamics , Containers , Cooling , Manufacturing , Temperature

Predicting Thermal Mixing and Fatigue Inside Control Rod Guide Tubes

Eric Lillberg

ICONE 2013; V003T10A042https://doi.org/10.1115/ICONE21-16632

Abstract

View Articletitled, Predicting Thermal Mixing and Fatigue Inside Control Rod Guide Tubes

PDF

Topics: Fatigue , Water , Flow (Dynamics) , Oscillations , Temperature , Computational fluid dynamics , Jets , Nuclear power stations , Rods , Stress

A Numerical Simulation on Effects of Distance Between Bubble and the Wall on Behavior of Rising Bubble

Ying Huang, Puzhen Gao

ICONE 2013; V003T10A043https://doi.org/10.1115/ICONE21-16641

Abstract

View Articletitled, A Numerical Simulation on Effects of Distance Between Bubble and the Wall on Behavior of Rising Bubble

PDF

Topics: Bubbles , Computer simulation , Surface tension

The Modelling and Coupling Methodology of ANSYS CFX Using Porous Media for PB-AHTR

Linsen Li, Haomin Yuan, Kan Wang

ICONE 2013; V003T10A044https://doi.org/10.1115/ICONE21-16687

Abstract

View Articletitled, The Modelling and Coupling Methodology of ANSYS CFX Using Porous Media for PB-AHTR

PDF

Topics: Modeling , Porous materials , Steady state , Computational fluid dynamics , High temperature , Thermal hydraulics

Multiphysics Analysis System for Tube Failure Accident in Steam Generator of Sodium-Cooled Fast Reactor

Akihiro Uchibori, Shin Kikuchi, Akikazu Kurihara, Hirotsugu Hamada, Hiroyuki Ohshima

ICONE 2013; V003T10A045https://doi.org/10.1115/ICONE21-16692

Abstract

View Articletitled, Multiphysics Analysis System for Tube Failure Accident in Steam Generator of Sodium-Cooled Fast Reactor

PDF

Topics: Accidents , Boilers , Failure , Sodium fast reactors , Computer simulation , Heat transfer , Chemical reactions , Sodium , Water , Computers

Effects of Bypass Flow on the LOFA Transient Computations in a VHTR

Yu-Hsin Tung, Richard W. Johnson, Yuh-Ming Ferng, Ching-Chang Chieng

ICONE 2013; V003T10A046https://doi.org/10.1115/ICONE21-16768

Abstract

View Articletitled, Effects of Bypass Flow on the LOFA Transient Computations in a VHTR

PDF

Topics: Computation , Flow (Dynamics) , Transients (Dynamics) , Very high temperature reactors , Coolants , Computational fluid dynamics , Heat , Accidents , Cooling , Fuels

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